Evaluation of heat removal property in W/Cu/RAFM steel joint by using electron beam facility-Reference-Cited by-同舟云学术

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Evaluation of heat removal property in W/Cu/RAFM steel joint by using electron beam facility

Published:2022-10 Issue: Volume:33 Page:101236
ISSN:2352-1791
Container-title:Nuclear Materials and Energy
language:en
Short-container-title:Nuclear Materials and Energy

Author:

Yamashita T.,Tokitani M.,Hamaji Y.,Shen J.,Noto H.,Masuzaki S.,Muroga T.

Funder

National Institute for Fusion Science

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics

Reference14 articles.

1. Helical reactor design FFHR-d1 and c1 for steady-state DEMO

2. Formularization of the confinement enhancement factor as a function of the heating profile for FFHR-d1 core plasma design

3. Potential of Copper Alloys using a Divertor Heat Sink in the Helical Reactor FFHR-d1 and their Brazing Properties with Tungsten Armor by using the Typical Candidate Filler Materials

4. Studies of power exhaust and divertor design for a 1.5 GW-level fusion power DEMO

5. Fabrication of divertor mock-up with ODS-Cu and W by the improved brazing technique

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Improving interfacial microstructure and mechanical properties of ODS-W/Cu joints via anodization treatment and spark plasma sintering;Journal of Nuclear Materials;2024-12

2. Multi-factor coupled failure mechanism of W–Cu functionally graded material under thermal shock service;Journal of Materials Research and Technology;2023-11

3. Recent progress in research on bonding technologies of W/Cu monoblocks as the divertor for nuclear fusion reactors;Nuclear Materials and Energy;2023-09

4. Evaluation of Tungsten—Steel Solid-State Bonding: Options and the Role of CALPHAD to Screen Diffusion Bonding Interlayers;Metals;2023-08-10

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